ML20080K636
| ML20080K636 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/10/1984 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20080K639 | List: |
| References | |
| TAC-53266, TAC-54234, NUDOCS 8402160088 | |
| Download: ML20080K636 (2) | |
Text
/E E
. Memng Addr:ss Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291
. Telephone 205 783-6081 F. L. Clayton, Jr.
Senior Vice President
- Fhntridge Building MDb8[Il3 bWCf
" S "'*" **c S**
February 10, 1984
-Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington,'D.C. 20555 Attention:
-Mr.-S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Proposed Technical Specification Change to Reactor Coolant System Pressure and Temperature Requirements r
Gentlemen:
Alabama Power Company letter dated November 10, 1983 forwarded reactor vessel surveillance capsule test results for Unit 2 and cormnitted to submit associated technical specification changes within 90 days in accordance with 10CFR50, Appendix H, Paragraph III.C. The test results were detailed in WCAP-10425, " Analysis of Capeule U from the Alabama Power Company Joseph M.
- Farley Unit 2 Reactor Vessel Radiation Surveillance Program," which was
+
attached to the November 10, 1983 letter. Proposed technical specification changes are contained herein based on WCAP-10425 and recent changes to T
10CFR50,- Appendix H (48FR24008 dated May 31, 1983).
Attached are proposed changes to Technical Specification Tables 4.4-5, Figures 3.4-2-and 3.4-3 and Bases 3/4.4. The changes to Table 4.4-5,
" Reactor Vessel Material Surveillance Program - Withdrawal Schedule,"
l include new lead factors and a _ revised capsule withdrawal sequence and schedule. The new lead factors are based on plant operating history, fast-neutron monitoring data and analytical evaluations of the data as discussed in~WCAP-10425 Section 6, " Radiation Analysis and Neutron Dosimetry." The revised capsule withdrawal schedule is based on the new i-lead factors and results of the analysis of Capsule U as presented in
' WCAP-10425. Section 7, " Surveillance Capsule Removal Schedule."
The proposed changes to Technical Specification Tables 3.4-2 and 3.4-3 on' pressure-temperature limits are administrative in nature. The current technical specification tables are labeled as applicable for the service g
. period up to 5 EFPY and contains margins of 10*F and 60 psig for possible
' instrument errors. The 5 EFPY service period does not include margins
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Mr. S. A. Varga February 10, 1984 U. S. Nuclear Regulatory Commission Page 2 for instrument errors and becomes 4.3 EFPY when instrument errors are incl uded. Furthermore, the RTndt after 4.3 EFPY for 3/4 T is 57*F rather than the 90*F as indicated in the existing tables. The proposed change corrects these errors.
An additional change to the Basis of Technical Specification 3/4.4 is proposed to conform with the recent change to 10CFR50, Appendix H (48FR24008 dated May 31, 1983). The change involves updating the references to ASTM E 185-73 to ASTM E 185-82 to reflect the rule change.
The proposed changes described herein do not involve a Significant Hazards Consideration as defined in 10CFR50.92; The changes are similar to examples (1) and (vi) of " Examples of Amendments That Are Considered Not Likely To Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6,1983. The changes are similar to example (vi) in that the changes to Table 4.4-5 and Bases 3/4.4 are " clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan" and similar to example (i) in that the change to Table 3.4-2 and 3.4-3 is "a purely administrative change to technical specifications:
for example, a change to achieve... correction of an error."
The Plant Operations Review Connittee has reviewed this proposed change. The Nuclear Operations Review Board will review this proposed change at a future meeting.
This proposed technical specification change is considered to be a C1 ass III admendment for Unit 2 in accordance with 10CFR170.22.
A check for $4,000.00 is~therefore enclosed.
In accordance with the 1984 Alabama Power Company licensing plan previously discussed with the NRC Staff, NRC approval of this change is requested by February 10, 1985.
In accordance with 10CFR50.90, three (3) signed originals and 40 copies of this proposed change are enclosed. As noted by the distribution, a copy of this letter is being sent to the Alabama State Designee in accordance with 10CFR50.91(b)(1).
If there are any questions, please advise.
Yours very truly, Yh F. L. Clayto, Jr.
I FLCJ r/GGY:l sh-D37 SWORN TO AND SUBSCRIBID BEF,0RE ME Attachments THIS lotL DAY Of::lL%utV,1984 cc: Mr. R. A. Thomas W
Mr. G. f. Trowbridge Mr..J. P. O' Reilly k
Mr. E. A. Reeves Notary Public Mr. W. H. Bradford Dr. I. L. Myers My Commission Expires: l-l047